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Small Spherical and their potential role in development of

Dr David Kingham, Nuclear Futures, 26 March 2013

Plasma in START , Courtesy Euratom/CCFE Fusion Association

March 2013 © Tokamak Solutions UK Ltd 2013 1 Introduction

• Tokamak Solutions UK Ltd was established “to make fusion useful quickly” by developing spherical tokamaks and powerful fusion sources • Based at , the world leading centre for fusion (JET) with unique capabilities in compact “Spherical Tokamaks” (MAST, START) • The mainstream world fusion programme is focussed on a long term goal of developing fusion as an energy source using large tokamaks • Recent breakthroughs in manufacturing of high temperature superconductors mean we can now see a possible way to achieve a high magnetic field in a small spherical tokamak • Such devices could help to accelerate the development of fusion energy A record breaking in the START spherical tokamak. The plasma diameter is < 1.5m.

March 2013 © Tokamak Solutions UK Ltd 2013 2 Some facts about fusion power

• There are two main candidates: magnetic and inertial confinement • Magnetic confinement is the most promising: there are several variants including , and Tokamaks. • Tokamaks have by far the best performance: JET at Culham produced 16MW fusion power in a short pulse in 1998. • The fuel (deuterium and ) is cheap and plentiful • JET is a large conventional tokamak; ITER is even larger. ITER tokamak: 35m high; €15bn cost; due to demonstrate fusion power in 2027

March 2013 © Tokamak Solutions UK Ltd 2013 3 Why are spherical tokamaks so exciting?

• Spherical Tokamaks (STs) can be small and straightforward to build • STs are close enough to the mainstream to be confident of the science, but distinctive enough to allow development of proprietary technology • STs use a magnetic field much more effectively than a conventional tokamak • If only it was possible to achieve a high magnetic field in a small spherical tokamak…

March 2013 © Tokamak Solutions UK Ltd 2013 4 High Temperature Superconductors (HTS)

Recent developments in ‘High Temperature’ superconductors could have far-reaching implications

At first, these were just thought to be a more convenient form of LTS in that they give similar performance but at around 77K (liquid nitrogen) rather than 4K (liquid helium) temperatures.

March 2013 © Tokamak Solutions UK Ltd 2013 5 Properties of HTS…

HTS has a remarkably high critical current at high field and low temperature

Example: in a field of 5T, HTS at 20K can pass 100 times as much current as at 77K

March 2013 © Tokamak Solutions UK Ltd 2013 6 Using HTS magnets on a tokamak

We have performed the first test of an HTS magnet on a tokamak, by fitting two HTS poloidal field coils on the GOLEM tokamak at Prague.

Upper PF coil cryostat winding the coil filling with liquid nitrogen

We are now running the ST25, a small test tokamak, and plan (in conjunction with Oxford Instruments) to test out a full magnet system wound from HTS. We are also designing high field HTS-based Spherical Tokamaks

March 2013 © Tokamak Solutions UK Ltd 2013 7 ST25 (copper coils)

RF waveguide (EBW plasma current drive experiments)

8 limbs, each 14 turns; the high inductance together with the high capacitance of our ‘supercapacitors’ (8F) provides pulses > 2s

Development programme includes: • Conversion to HTS (High Temperature Superconducting) magnets • Studies of RF start-up and ramp-up via EBW (Electron Bernstein Waves) 2-s long RF pulse

March 2013 © Tokamak Solutions UK Ltd 2013 8 ST25 with HTS cryostats

This 6-turn cryostat has the returns at large enough radius to minimise field ripple and provide aperture to insert and assemble vac vessel

Approx cost of HTS tape: $100k

March 2013 © Tokamak Solutions UK Ltd 2013 9 Conclusion

• Small Spherical Tokamaks can be built relatively easily and cheaply • They are exciting because they use a magnetic field efficiently • It now looks possible to design and build high field spherical tokamaks • Such devices could help to accelerate the development of fusion energy

Courtesy Euratom /CCFE Fusion Association

March 2013 © Tokamak Solutions UK Ltd 2013 10